HECTR (Hydrogen Event Containment Transient Response) Version 1. 5N: A modification of HECTR Version 1. 5 for application to N Reactor
Technical Report
·
OSTI ID:6260591
This report describes HECTR Version 1.5N, which is a special version of HECTR developed specifically for application to the N Reactor. HECTR is a fast-running, lumped-parameter containment analysis computer program that is most useful for performing parametric studies. The main purpose of HECTR is to analyze nuclear reactor accidents involving the transport and combustion of hydrogen, but HECTR can also function as an experiment analysis tool and can solve a limited set of other types of containment problems. Version 1.5N is a modification of Version 1.5 and includes changes to the spray actuation logic, and models for steam vents, vacuum breakers, and building cross-vents. Thus, all of the key features of the N Reactor confinement can be modeled. HECTR is designed for flexibility and provides for user control of many important parameters, if built-in correlations and default values are not desired.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6260591
- Report Number(s):
- SAND-87-0027; UNI-4332; ON: DE87012071
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900 -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220* -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
CHEMICAL REACTION KINETICS
CHEMICAL REACTIONS
COMBUSTION
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
ELEMENTS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GRAPHITE MODERATED REACTORS
H CODES
HEAT TRANSFER
HYDROGEN
KINETICS
LWGR TYPE REACTORS
N-REACTOR
NONMETALS
OXIDATION
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
REACTION KINETICS
REACTOR ACCIDENTS
REACTORS
SIMULATION
SYSTEMS ANALYSIS
THERMOCHEMICAL PROCESSES
TRANSPORT
WATER COOLED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900 -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220* -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
CHEMICAL REACTION KINETICS
CHEMICAL REACTIONS
COMBUSTION
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
ELEMENTS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GRAPHITE MODERATED REACTORS
H CODES
HEAT TRANSFER
HYDROGEN
KINETICS
LWGR TYPE REACTORS
N-REACTOR
NONMETALS
OXIDATION
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
REACTION KINETICS
REACTOR ACCIDENTS
REACTORS
SIMULATION
SYSTEMS ANALYSIS
THERMOCHEMICAL PROCESSES
TRANSPORT
WATER COOLED REACTORS